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Oxidative dissolution of ADOPT compared to standard UO2 fuel
KTH, School of Chemical Science and Engineering (CHE), Chemistry, Applied Physical Chemistry.
KTH, School of Chemical Science and Engineering (CHE), Chemistry, Applied Physical Chemistry.ORCID iD: 0000-0003-0663-0751
2017 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 488, p. 123-128Article in journal (Refereed) Published
Abstract [en]

In this work we have studied oxidative dissolution of pure UO2 and ADOPT (UO2 doped with Al and Cr) pellets using H2O2 and gammaradiolysis to induce the process. There is a small but significant difference in the oxidative dissolution rate of UO2 and ADOPT pellets, respectively. However, the difference in oxidative dissolution yield is insignificant. Leaching experiments were also performed on in-reactor irradiated ADOPT and UO2 pellets under oxidizing conditions. The results indicate that the U(VI) release is slightly slower from the ADOPT pellet compared to the UO2. This could be attributed to differences in exposed surface area. However, fission products with low UO2 solubility display a higher relative release from ADOPT fuel compared to standard UO2-fuel. This is attributed to a lower matrix solubility imposed by the dopants in ADOPT fuel. The release of Cs is higher from UO2 which is attributed to the larger grain size of ADOPT. © 2017 Elsevier B.V.

Place, publisher, year, edition, pages
Elsevier B.V. , 2017. Vol. 488, p. 123-128
Keyword [en]
Doping (additives), Fission products, Fuels, Pelletizing, Solubility, Exposed surfaces, Grain size, Leaching experiments, Matrix solubility, Oxidative dissolution, Oxidizing conditions, Dissolution
National Category
Physical Chemistry
Identifiers
URN: urn:nbn:se:kth:diva-207344DOI: 10.1016/j.jnucmat.2017.02.044ISI: 000400218100012Scopus ID: 2-s2.0-85015707126OAI: oai:DiVA.org:kth-207344DiVA, id: diva2:1097352
Note

QC 20170522

Available from: 2017-05-22 Created: 2017-05-22 Last updated: 2017-05-23Bibliographically approved

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Jonsson, Mats

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